Design and Assembly of MiniFuel Targets for Characterization of High Burnup UO2 Specimens Irradiated in the High Flux Isotope Reactor ORNL Report June, 2024
Hypothetical Sodium-Cooled Fast Reactor Fuel Transport Using the Existing ES-3100... ORNL Report May, 2024
SCALE 6.3 Modeling Strategies for Reactivity, Nuclide Inventory, and Decay Heat of Non-LWRs ORNL Report May, 2024
Samoa Updater: An Application of the Levenberg-Marquardt Method to Update Delfic Predictions Using Field Measurements ORNL Report May, 2024
Comparison of Temperature-Dependent Cross Section Treatments Within the Shift Monte Carlo Radiation Transport Code... ORNL Report April, 2024
SCALE 6.3.1 Radiation Source Terms and Shielding Analysis for a Postulated Sodium-Cooled Fast Reactor Accident Scenario Conference Paper April, 2024
Scoping Studies on the Impacts of Increased Enrichment on Nuclear Criticality Safety ORNL Report April, 2024
